Using MELCOR with enhanced predictive capabilities via thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl

Breeden, B.; Poschmann, M.; Piro, M. H. A.

doi:10.1016/j.nucengdes.2024.112957

Title: Using MELCOR with enhanced predictive capabilities via thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl

Journal Article · 01 April 2024 · Nuclear Engineering and Design

DOI: https://doi.org/10.1016/j.nucengdes.2024.112957 · OSTI ID:2368947

Breeden, B.;

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Sponsoring Organization:: USDOE

OSTI ID:: 2368947

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: C Vol. 419; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: Netherlands

Language:: English

References (10)

UO2/Zircaloy-4 chemical interactions from 1000 to 1700°C under isothermal and transient temperature conditions Hofmann, P.; Kerwin-Peck, D. Journal of Nuclear Materials, Vol. 124 https://doi.org/10.1016/0022-3115(84)90013-8	journal	May 1984
Modification of the two-sublattice model for liquids Sundman, Bo Calphad, Vol. 15, Issue 2 https://doi.org/10.1016/0364-5916(91)90010-H	journal	April 1991
The objectives of the Phébus FP experimental programme and main findings Clément, Bernard; Zeyen, Roland Annals of Nuclear Energy, Vol. 61 https://doi.org/10.1016/j.anucene.2013.03.037	journal	November 2013
The thermochemistry library Thermochimica Piro, M. H. A.; Simunovic, S.; Besmann, T. M. Computational Materials Science, Vol. 67 https://doi.org/10.1016/j.commatsci.2012.09.011	journal	February 2013
Accident tolerant fuel cladding development: Promise, status, and challenges Terrani, Kurt A. Journal of Nuclear Materials, Vol. 501 https://doi.org/10.1016/j.jnucmat.2017.12.043	journal	April 2018
Contribution to the thermodynamic description of the corium – The U-Zr-O system Quaini, A.; Guéneau, C.; Gossé, S. Journal of Nuclear Materials, Vol. 501 https://doi.org/10.1016/j.jnucmat.2018.01.023	journal	April 2018
Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan Sakamoto, K.; Miura, Y.; Ukai, S. Journal of Nuclear Materials, Vol. 557 https://doi.org/10.1016/j.jnucmat.2021.153276	journal	December 2021
Material Interactions in Severe Accidents – Benchmarking the MELCOR V2.2 Eutectics Model for a BWR-3 MARK-I Station Blackout: Part I – Single Case Analysis Albright, Lucas I.; Andrews, Nathan; Humphries, Larry L. Nuclear Engineering and Design, Vol. 382 https://doi.org/10.1016/j.nucengdes.2021.111292	journal	October 2021
Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants Rebak, Raul B. EPJ Nuclear Sciences & Technologies, Vol. 3 https://doi.org/10.1051/epjn/2017029	journal	January 2017
Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms Gelbard, Fred; Beeny, Bradley A.; Humphries, Larry L. Nuclear Science and Engineering, Vol. 197, Issue 10 https://doi.org/10.1080/00295639.2022.2161277	journal	June 2023

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